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Mechanical testing of a FW panel attachment system for ITER
Authors:Vladislav Oliva  Jaroslav Vclavík  Ale&#x; Materna  Patrick Lorenzetto  Andreas Furmanek
Affiliation:aCzech Technical University in Prague – FNSPE, Prague, Czech Republic;bŠKODA VÝZKUM s.r.o. (ŠKODA RESEARCH Ltd.), Pilsen, Czech Republic;cFusion For Energy, Barcelona, Spain;dEFDA, Garching, Germany
Abstract:An objective of experiments and finite element simulations was to check the stiffness, the strength and the fatigue resistance of the attachment of the First Wall panels onto a shield block of blanket modules according to the ITER 2001 design. The panel has a poloidal key at the rear side (in so-called option A with the rear access bolting) and it is attached by means of special studs located on a key-way in the shield block. Special device for a test of stud tensile pre-load relaxation during a thermal cycling was developed. True-to-scale panels, the shield block mock-up and simplified studs were fabricated and the assembly was loaded alternatively by radial moment, poloidal force or poloidal moment simulating the loading during off-normal plasma operations. Thermal cycling led to an acceptable stud pre-load relaxation. Mechanical cycling caused neither the pre-load relaxation nor the loss of the contact in the key-way nor a damage of the attachment system. The combination of poloidal moment and radial force during vertical displacement events (VDEs) seems to be a most dangerous case because it could lead to the loss of the key–key-way contact.
Keywords:ITER  Mechanical structures in vessel  First Wall  Panel attachment system
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